SAS4A analysis of unprotected loss of flow accidents in a metal fuel reactor

Conference · Tue Dec 01 04:00:00 EST 1992

OSTI ID:10111677

Tentner, A M

This paper discusses the SAS4A code system which is used to analyze the core behavior under beyond-design-base transient conditions for various Advanced Liquid Metal Reactor (ALMR) designs. The results of these analyses provide help in assessing the outcomes of various accident sequences, and provide guidance for future experimental needs and mathematical model development. This paper describes the thermal-hydraulic and neutronic events that occur in a low void worth metal fuel core [2] during a very rapid unprotected Loss of Flow (LOF) accident, with a flow decay half time t{sub 1/2} = 0.3s. This LOF was selected because it leads to fuel pin failure and subsequent fuel relocation. The only mechanistic initiator that can lead to such a rapid LOF is, possibly, a severe earthquake. For slower LOFs pin failure and fuel relocation do not occur, as negative reactivity from other core feedback effects has enough time to counteract the positive reactivity introduced by the early sodium boiling.

• Research Organization: Argonne National Lab., IL (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 10111677
• Report Number(s): ANL/CP--76288; CONF-921102--42; ON: DE93004242
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
99 GENERAL AND MISCELLANEOUS
990200
BOILING
FAILURES
FUEL PINS
HEAT TRANSFER
HYDRAULICS
LMFBR TYPE REACTORS
LOSS OF FLOW
MATHEMATICS AND COMPUTERS
POWER REACTORS
BREEDING
REACTIVITY
REACTOR SAFETY
S CODES